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Novel Strategy for Hazardous Cement Bypass Dust Removal: Structural, Optical and Nuclear Radiation Shielding Properties of CBD-Bismuth Borate Glass
Herein, this study introduced a novel strategy for hazardous cement bypass dust (CBD) removal via incorporated it into glassy system having the chemical formula 10Li 2 O–10Bi 2 O 3 –(80 − x)B 2 O 3 –xCBD, where x = 0, 10, 20 and 30%. The doped glass samples with the CBD were used as a radiation shie...
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Published in: | Journal of inorganic and organometallic polymers and materials 2022-09, Vol.32 (9), p.3533-3545 |
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Main Authors: | , , , , |
Format: | Article |
Language: | English |
Subjects: | |
Citations: | Items that this one cites Items that cite this one |
Online Access: | Get full text |
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Summary: | Herein, this study introduced a novel strategy for hazardous cement bypass dust (CBD) removal via incorporated it into glassy system having the chemical formula 10Li
2
O–10Bi
2
O
3
–(80 − x)B
2
O
3
–xCBD, where x = 0, 10, 20 and 30%. The doped glass samples with the CBD were used as a radiation shielding material. The structural, optical and nuclear radiation shielding properties of CBD-lithium bismuth borate (LBB) glass were investigated. The optical energy gap increases from 2.22 eV for LBB + 0% CBD glass sample to 2.66 eV for LBB + 30% CBD glass sample. Also, a comparative study between the experimental data and theoretical interpretation for the attenuation coefficients was addressed via the Phy-X software database. The outcomes unveiled that the shielding parameters such as the linear attenuation coefficient, mass attenuation coefficient, and the effective atomic number were enhanced as CBD content increases. In the same time, the half-value layer, the tenth value layer, and the mean free path are reduced with the enrichment in the CBD content. Furthermore, the exposure build-up factor is inversely related to equivalent atomic numbers. Based on these findings, it was determined that the manufactured bismuth lithium-borate glass system doped cement bypass dust can be used for radiation shielding purposes. |
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ISSN: | 1574-1443 1574-1451 |
DOI: | 10.1007/s10904-022-02378-x |